Contents

Physics of Atomic Nuclei

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Vol. 79, No. 8, 2016

A simultaneous English language translation of this journal is available from Pleiades Publishing, Ltd.
Distributed worldwide by Springer. Physics of Atomic Nuclei ISSN 1063-7788.

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Algorithm for Solving the Linear Cauchy Problem for Large Systems of Ordinary Differential Equations with the Use of Parallel Computations

A. V. Moryakov p. 1233  abstract

LUCKY_TD Code for Solving the Time-Dependent Transport Equation with the Use of Parallel Computations

A. V. Moryakov p. 1242  abstract

Parallelization of Heterogeneous Reactor Calculations on a Graphics Processing Unit

V. M. Malofeev and V. A. Pal’shin p. 1246  abstract

Time-Dependent Integral Equations of Neutron Transport for Calculating the Kinetics of Nuclear Reactors by the Monte Carlo Method

V. D. Davidenko, A. S. Zinchenko and I. K. Harchenko p. 1252  abstract

Effective Conditions for the Neutron Flux Density at Axial Boundaries of the Core

E. A. Aristarkhova and V. M. Malofeev p. 1257  abstract

Generalization of Two-Dimensional DDL Schemes of the GQ Method for Three-Dimensional Arbitrary Hexahedral Spatial Mesh

A. A. Nikolaev p. 1261  abstract

Criticality Calculation of Non-Ordinary Systems

A. V. Kalugin and V. V. Tebin p. 1267  abstract

Shaping of the Axial Power Density Distribution in the Core to Minimize the Vapor Volume Fraction at the Outlet of the VVER-1200 Fuel Assemblies

V. I. Savander, B. E. Shumskiy and A. A. Pinegin p. 1279  abstract

On the Equilibrium Isotopic Composition of the Thorium–Uranium–Plutonium Fuel Cycle

V. Ye. Marshalkin and V. M. Povyshev p. 1290  abstract

The Influence of Changes in the VVER-1000 Fuel Assembly Shape during Operation on the Power Density Distribution

L. K. Shishkov, S. S. Gorodkov, E. F. Mikailov, E. A. Sukhino-Homenko and A. S. Sumarokova p. 1298  abstract

Analysis of the Uncertainties in the Physical Calculations of Water-Moderated Power Reactors of the VVER Type by the Parameters of Models of Preparing Few-Group Constants

V. V. Bryukhin, K. Yu. Kurakin and M. A. Uvakin p. 1305  abstract

Analysis of Features of Hydrodynamics and Heat Transfer in the Fuel Assembly of Prospective Sodium Reactor with a High Rate of Reproduction in the Uranium-Plutonium Fuel Cycle

A. S. Lubina, A. S. Subbotin, A. A. Sedov and A. A. Frolov p. 1315  abstract

A Method for Development of Efficient 3D Models for Neutronic Calculations of ASTRA Critical Facility Using Experimental Information

A. L. Balanin, V. F. Boyarinov, E. S. Glushkov, A. A. Zimin, G. V. Kompaniets, V. A. Nevinitsa, N. P. Moroz, P. A. Fomichenko, A. V. Timoshinov and Yu. N. Volkov p. 1325  abstract

Measuring the Efficiency of Control Rods in the RBMK Critical Assembly Using a Model of RKI-1 Reactimeter

V. E. Zhitarev, G. V. Lebedev and A. Yu. Sergevnin p. 1333  abstract

Feasibility of Creating a Specialized Reactimeter Based on the Inverse Solution to Kinetics Equation with a Current-Mode Neutron Detector

A. S. Koshelev, A. V. Arapov and M. A. Ovchinnikov p. 1340  abstract

Wide-Range Structurally Optimized Channel for Monitoring the Certified Power of Small-Core Reactors

A. S. Koshelev, K. N. Kovshov, M. A. Ovchinnikov, G. N. Pikulina and A. B. Sokolov p. 1349  abstract

Measurement of Prompt Neutron Generation Time at the VIR-2M Pulsed Nuclear Reactor

L. Yu. Glukhov, S. P. Kotkov, M. S. Kuznetsov and S. S. Chursin p. 1357  abstract

A Setup for Active Neutron Analysis of the Fissile Material Content in Fuel Assemblies of Nuclear Reactors

A. V. Bushuev, A. F. Kozhin, T. B. Aleeva, V. N. Zubarev, E. V. Petrova and V. E. Smirnov p. 1362  abstract

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